Optimization of multidimensional cross-section tables for few-group core calculations

Sánchez-Cervera Huerta, Santiago and García Herranz, Nuria and Herrero Carrascosa, José Javier and Cabellos de Francisco, Oscar Luis (2014). Optimization of multidimensional cross-section tables for few-group core calculations. "Annals of Nuclear Energy", v. 69 (n. null); pp. 226-237. ISSN 0306-4549. https://doi.org/10.1016/j.anucene.2014.02.013.

Description

Title: Optimization of multidimensional cross-section tables for few-group core calculations
Author/s:
  • Sánchez-Cervera Huerta, Santiago
  • García Herranz, Nuria
  • Herrero Carrascosa, José Javier
  • Cabellos de Francisco, Oscar Luis
Item Type: Article
Título de Revista/Publicación: Annals of Nuclear Energy
Date: July 2014
ISSN: 0306-4549
Volume: 69
Subjects:
Freetext Keywords: Tabulated cross sections library; Optimization; Grid point distribution
Faculty: E.T.S.I. Industriales (UPM)
Department: Ingeniería Energética
Creative Commons Licenses: Recognition - No derivative works - Non commercial

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Abstract

Multigroup diffusion codes for three dimensional LWR core analysis use as input data pre-generated homogenized few group cross sections and discontinuity factors for certain combinations of state variables, such as temperatures or densities. The simplest way of compiling those data are tabulated libraries, where a grid covering the domain of state variables is defined and the homogenized cross sections are computed at the grid points. Then, during the core calculation, an interpolation algorithm is used to compute the cross sections from the table values. Since interpolation errors depend on the distance between the grid points, a determined refinement of the mesh is required to reach a target accuracy, which could lead to large data storage volume and a large number of lattice transport calculations. In this paper, a simple and effective procedure to optimize the distribution of grid points for tabulated libraries is presented. Optimality is considered in the sense of building a non-uniform point distribution with the minimum number of grid points for each state variable satisfying a given target accuracy in k-effective. The procedure consists of determining the sensitivity coefficients of k-effective to cross sections using perturbation theory; and estimating the interpolation errors committed with different mesh steps for each state variable. These results allow evaluating the influence of interpolation errors of each cross section on k-effective for any combination of state variables, and estimating the optimal distance between grid points.

Funding Projects

TypeCodeAcronymLeaderTitle
Government of SpainP110530207CSNUnspecifiedSpanish Nuclear Safety Council (CSN)
FP7323263NURESAFEUnspecifiedNuclear Reactor Safety Simulation Platform

More information

Item ID: 35635
DC Identifier: http://oa.upm.es/35635/
OAI Identifier: oai:oa.upm.es:35635
DOI: 10.1016/j.anucene.2014.02.013
Official URL: http://www.journals.elsevier.com/annals-of-nuclear-energy/
Deposited by: Memoria Investigacion
Deposited on: 22 Sep 2015 14:11
Last Modified: 22 May 2019 07:25
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